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OECD NEA meeting focuses on irradiation experiments
Members of the OECD Nuclear Energy Agency’s Second Framework for Irradiation Experiments (FIDES-II) joint undertaking gathered from September 29 to October 3 in Ketchum, Idaho, for the technical advisory group and governing board meetings hosted by Idaho National Laboratory. The FIDES-II Framework aims to ensure and foster competences in experimental nuclear fuel and structural materials in-reactor experiments through a diverse set of Joint Experimental Programs (JEEPs).
M. Fujiwara
Fusion Science and Technology | Volume 27 | Number 3 | April 1995 | Pages 58-70
Overview Paper | doi.org/10.13182/FST95-A11947047
Articles are hosted by Taylor and Francis Online.
Recent research has made significant progress for the plasma confinement in helical systems. Experiments have been carried out in W7AS, CHS, ATF, H-E and others. The plasmas, whose electron temperature is around 2–3keV, ion temperature is 1 keV and density is 2–3×1020 m-3, are well confined with the energy confinement time τ E =10–40ms and the stable beta value reaches at < β >> 2% (β (0)=7%)[1]. The obtained scalings for the global energy confinement time such as LHD, GRB(Gyro-Reduced Bohm), L-G(Lackner-Gottardi) scalings are comparable with the tokamak L-mode scaling in the above parameters' range. The improved confinement modes are also explored in helical systems as H mode or the control of plasma profile.
In this paper, firstly present experimental results are reviewed on the confinement, MHD equilibrium/stability beta limit, and secondly the outline of LHD and W7X program is described.
Finally, is discussed the feasibility of helical systems as a fusion reactor, based on the present experimental results.